- For the first time in a spherical tokamak, small magnetic
coils have been used to stabilise instabilities in fusion plasmas
- Researchers have demonstrated independent control of upper
and lower divertors, opening new capabilities for future fusion
power plants
- The fourth campaign also achieved the best plasma shape ever
recorded within the machine, a major factor in improving plasma
performance
In a major breakthrough for fusion energy research, scientists at
the UK Atomic Energy Authority (UKAEA) have used magnetic coils
to apply a 3D magnetic field and stabilise instabilities in a
spherical tokamak plasma for the first time. This achievement
marks a significant step forward in the development of
sustainable fusion energy within spherical tokamaks.
To achieve fusion using Mega Amp Spherical Tokamak (MAST)
Upgrade, fusion fuel needs to be confined at high temperature
within the tokamak to create a plasma.
If the plasma current, pressure or density is too high, the
plasma can become unstable, reducing performance or risking
damage to tokamak components. Maintaining plasma stability is one
of fusion's key challenges.
Edge Localised Modes (ELMs) are instabilities that occur at the
edge of a plasma and could pose a serious challenge to the inner
components of a future fusion power plant. Using Resonant
Magnetic Perturbation (RMP) coils – which apply a small 3D
magnetic field at the plasma edge – UKAEA researchers have
demonstrated complete suppression of ELMs within the MAST Upgrade
machine. This is the first time such suppression has been
evidenced in a spherical tokamak.
, Head of MAST Upgrade
Science at UKAEA, said:
Suppressing ELMs in a spherical tokamak is a landmark
achievement. It is an important demonstration that advanced
control techniques developed for conventional tokamaks can be
successfully adapted to compact configurations to develop the
scientific basis for future power plants like STEP, the Spherical
Tokamak for Energy Production.
MAST Upgrade, the largest spherical tokamak operating in the
world, is designed in the shape of a cored apple, in contrast to
other ring-shaped tokamaks. These findings were part of MAST
Upgrade's fourth scientific campaign, focused on plasma
properties and controlling plasma exhaust.
Further work is planned in the next MAST Upgrade experimental
campaign to verify and expand on this world-first finding. In
time, these results will directly inform the design of ELM
control systems for the UK's STEP Fusion programme. In addition,
they will also help to eliminate ELMs as a barrier to commercial
fusion viability.
Advancing plasma exhaust solutions
In another world first, UKAEA researchers have demonstrated that
they can independently control the plasma exhaust in the upper
and lower divertors in MAST Upgrade without impacting the
performance or density of the plasma in the main chamber of the
tokamak.
A tokamak exhaust system – known as a divertor – takes the
particles and heat ejected from the plasma and directs it onto
surfaces within the tokamak. Managing plasma exhaust is another
key fusion challenge, and the ability to independently control
upper and lower divertors in a tokamak could significantly
enhance the robustness and flexibility of future power plant
operations.
Additionally, experiments involving nitrogen injection at the
plasma edge have shown that energy can be more evenly distributed
across plasma-facing components. This technique prevents
excessive heat concentration and opens a new path for managing
power exhaust in compact spherical tokamaks, bringing them in
line with advanced exhaust solutions being explored in
conventional aspect ratio machines.
Record performance and plasma shaping
MAST Upgrade also set a record for power injected into its
plasma, reaching 3.8 megawatts using neutral beam heating. This
milestone supports higher performance plasma scenarios and
contributes to the development of power plant-relevant
conditions.
In the latest round of experiments, the team also achieved the
best plasma shape ever recorded on the machine, with an
elongation of 2.5 – meaning the plasma height is 2.5 times its
width.
The shaping of a plasma can have a stabilising effect, enabling
higher-performance plasmas which have higher pressure and better
confinement. Greater plasma elongation, or height divided by
width, improves plasma performance and will be a key target for
future fusion power plants like STEP.
Fulvio Militello, Executive Director of Plasma Science and Fusion
Operations, UKAEA, said:
I'm delighted with the ground-breaking findings from our team at
UKAEA. These achievements reinforce the UK's leadership in fusion
research and bring us closer to realising fusion as a clean,
safe, and abundant energy source for the future.